RIAR as IAEA ICERR: Pilot Technical Cooperation Projects and Future - PowerPoint PPT Presentation

The 18th IGORR Conference 3-7 December 2017, The International Conference Centre, Darling Harbour, Sydney, Australia RIAR as IAEA ICERR: Pilot Technical Cooperation Projects and Future Prospects Alexander TUZOV JSC “SSC RIAR”, Director

General Information Foundation: March, 1956 Destination: airports with direct flights to / from Moscow, Saint-Petersburg and other cities - Samara (160 km), Ulyanovsk (90 km) Number of staff: 3 200 persons (incl. ~400 researchers) Customers: more than 25 countries Overseas Portfolio: more than USD 60 mln. RIAR’s Overview: World's largest fleet of nuclear research facilities (incl. five RRs and two critical stands) World’s largest complex for post -irradiation examination (incl. full-size fuel assemblies) Radiochemical complex to perform NFC-related research activities Complex to study properties and produce TRU elements; R&D and production of radionuclides with high specific activity and radiation sources Full-cycle infrastructure, incl. nuclear fuel production, spent nuclear fuel and radioactive waste management, treatment of minor actinides 2 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

RIAR as IAEA ICERR The RIAR’s application to IAEA ICERR status was supported by ROSATOM and submitted to the IAEA on June, 2016. The ICERR Audit Mission team was organized and headed by IAEA’s Research Reactor Section, Department of Nuclear Energy. During the visit to the RIAR’s site in July 2016 , Mr. Andrea Borio di Tigliole (Head of IAEA’s Research Reactor Section) RIAR’s noted wide experimental capabilities, its great expertise and high level of motivation of its employees. Designation of RIAR as the IAEA I nternational Ce ntre based on R esearch R eactors (ICERR) confirmed the worldwide recognition of JSC ”SSC RIAR” as a reputable research Official ceremony of RIAR Designation as IAEA ICERR (IAEA's 60th General Conference, organization. September 26, 2016) Perimeter of RIAR’s as IAEA ICERR: Sodium-cooled Fast Test Reactor BOR-60 Multi-Loop Research Reactor MIR.M1 High-Flu х Research Reactor SM-3 Two critical experimental facilities (the physical mockups of the RRs SM-3 and MIR.M1) BOR-60 MIR.M1 SM-3 Hot Lab Reactor Materials Testing Complex 3 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

RIAR’s Infrastructure Radionuclide Radiochemical Sources & Technology Radiochemicals Complex Division Reactor Materials Nuclear Fuel Research Reactors Testing Production Complex Complex &Technology Complex Spent Fuel & Labs, R&D, Radwaste Design & Management Engineering Complex Infrastructure RIAR is the unique facility ; its self-sufficient R&D and production complex allows providing Customers with full-cycle high tech services and to fulfill all the Customer’s requirements. 4 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

MIR.M1 Reactor Irradiation Capabilities of the MIR.M1 Tests of fuel 900 IV о С 800 rods of high- Температура оболочки твэла, Tests of fuel V 700 temperature III for fast 600 II gas-cooled 500 Температурная Tests of reactors область 400 эксперимента reactors RBMK-type 300 Тs I 200 fuel rods до 5 часов -300 -200 -100 0 100 200 300 400 500 600 Время,с Tests of VVER fuel assembly components Tests of fuel rods and fuel assemblies for floating and low- power reactors Tests of PWR-type Tests of fuel rods fuel rods and fuel assemblies for propulsion reactors Tests of structural materials of VVER- Tests of Accumulation type and PWR-type fuel rods and fuel of fuel assemblies assemblies of radioisotopes research reactors for various purposes 5 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

MIR.M1 Reactor Irradiation Capabilities of the MIR.M1 MIR.M1 Key Parameters Reactor type Channel-type water-cooled Max thermal capacity, MW 100 Max neutron flux density , с m -2  s -1 5  10 14 Core height, mm 1000 No of loop channels 11 230 ÷ 240 Effective days per year Planned life-time Till at least 2035 Loops Parameter PV-1 PVK-1 PV-2 PVK-2 PVP-1 PVP-2 PG-1 Water, Water, Water, Water, Boiling Boiling He, Coolant Water Boiling Water Boiling water, water, N 2 water water Steam Steam Number of channels 2 2 2 2 1 1 1 Max channel capacity, 1500 1500 1500 1500 100 2000 160 kW Max coolant 350 350 350 355 500 550 600 temperature,  С Max pressure, MPa 16,8 16,8 17,8 17,8 8,5 20,0 20,0 Max flow rate through 16,0 14,0 16,0 14,0 0,7 10,0 - the channel, t/h 6 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

BOR-60 Reactor Irradiation Capabilities of the BOR-60 BOR-60 Key Parameters Fast-neutron Reactor type sodium-cooled 60 Max thermal capacity, MW Max neutron flux density , с m -2  s -1 3,5·10 15 UO 2 - РuO 2 Fuel 45 ÷ 90 Enrichment in 235 U, % Enrichment in 239 Р u, % Up to 70 12 No of experimental cells 230 ÷ 240 Effective days per year Planned life-time More than 2020 7 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

BOR-60 Reactor Irradiation Capabilities of the BOR-60 Irradiation of promising fuels, absorbers and structural Simulation of Research focused materials, and steady-state and justification of their on improvement of transient performance the existing designs operational of fuel elements, conditions to test control rods, fuel nuclear reactors assemblies, etc. components Tests of new gages intended for Tests of new monitoring reactor process conditions of systems and reactor, fuel equipment assemblies and coolant 8 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

SM-3 Reactor Irradiation Capabilities of the SM-3 SM-3 Key Parameters Vessel-type water-cooled Reactor type with a trap Max thermal capacity, MW 100 Max neutron flux density , с m -2  s -1 5  10 15 Core height, mm 350 230 ÷ 240 Effective days per year Planned life-time Till at least 2035 Testing parameters Design of φ irradiation Medium Kt, φ , cm -2 ·s -1 (E>0,1 MeV), K, dpa/h rig dpa/year cm -2 ·s -1 Water (300  C, 3·10 -5 Loop rig in 10 13 ÷ 4·10 14 2·10 13 ÷ 4·10 14 0,15 ÷ 6,0 ÷ 1,2·10 -3 the reflector 18,5 MPa) Water (300  C, Loop rig in ≤ 3·10 -3 15 ÷ 18 1,5·10 15 2·10 14 the core 18,5 MPa) Boiling water (up Ampoule to 320  C), 1·10 -5 5·10 12 ÷ 4·10 1 2·10 13 ÷ 4·10 14 0,1 ÷ 6,0 rig in the ÷ 1,2·10 -3 4 supercritical water, reflector gas (400 ÷ 1500  C) Boiling water (up Ampoule to 320  C), (1,5 ÷ 2)·10 15 (2 ÷ 3)·10 15 ≤ 4·10 -3 16 ÷ 25 rig in the supercritical water, core gas (400 ÷ 2500  C) 9 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Reactor Testing of Fuel MIR.M1 Reactor. RAMP Test (Proceedings of 2017 Water Reactor Fuel Performance Meeting/ TopFuel 2017, 10-14 September 2017, Jeju Island, Korea, paper A-096, CD) q l , W/cm 500 dL, mm 5 1 400 4 300 3 2 200 2 100 1 0 0 0 10 20 30 40 50 60 70 Structure in the area of large t, h corrugation in the FSFR (max burnup Change of parameters during RAMP experiment. 44,7 MWd/kgU) tested under RAMP The maximal LHR (1) and readings of the elongation transducer (2) of FSFR (max burnup 44,5 MWd/kgU) D, % 2.00 5 4 2 1 1.75 1.50 3 1.25 1.00 0.75 0.50 0.25 0.00 -0.25 -0.50 Irradiation rig to test 0 100 200 300 400 500 LP, W/cm LP, W/sm full-size and Residual cladding deformation (D) and LHR of fuel rods with different maximal refabricated fuel rods burnups tested under RAMP. 1 - (38,9-44,7) MWd/kgU; 2 – 44,5 MWd/kgU; under RAMP 3 - 47 MWd/kgU; 4 - 48,4 MWd/kgU; 5 - (56,4-60,9) MWd/kgU 10 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Reactor Testing of Fuel MIR.M1 Reactor. LOCA Test (Proceedings of 2017 Water Reactor Fuel Performance Meeting/ TopFuel 2017, 10-14 September 2017, Jeju Island, Korea, paper A-088, CD) ТС 1 Shrou d Basket Insulato r 840 7 ТС 2 1 760 6 2 Temperature, °C 4 Pressure, MPa ТС 3 680 5 600 4 ТС 4 ТС 5 520 3 3 Heater 440 2 360 1 280 0 ТС 6 12:00 12:01 12:02 12:03 12:04 12:05 12:06 12:07 Pressur e gauge Time, hh:mm Rotation Change in the fuel cladding temperature by 90 о above the central (1), lower (2) and upper (3) spacer grids at 5…50 mm from the State of the fuel rod upper grid end. Change in gas pressure (4). after MIR-LOCA/50 experiment (X-ray) MIR-LOCA/50 experiment Irradiation rig to test a single fuel rod 11 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

Reactor Testing of Fuel MIR.M1 Reactor. Test of Research Reactor Fuel (Proceedings of RERTR 2016 - 37th International Meeting on Reduced Enrichment for Research and Test Reactors, 23-27 October 2016, Antwerpen, Belgium, CD) a) b) a) b) General view of experimental fuel assembly IRT-3M (a) Temperature distribution in the cross and experimental channel with EFA (b) section of EFA IRT-3M and experimental channel a) burnup = 0 %; b) burnup = 60% Pressure drop increase for EFA IRT-3M, kgf/cm 2 Pressure drop increase for EFA IRT-3M as a function of burnup range Flow rate, m 3 /h 12 The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia